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| | issue date = 09/18/1998 | | | issue date = 09/18/1998 |
| | title = Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems | | | title = Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems |
| | author name = Roe J W | | | author name = Roe J |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | page count = 7 | | | page count = 7 |
| }} | | }} |
| {{#Wiki_filter:~0- f9AcreUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001September 18, 1998NRC INFORMATION NOTICE 98-36: INADEQUATE OR POORLY CONTROLLED, NON-SAFETY-RELATED MAINTENANCE ACTIVITIESUNNECESSARILY CHALLENGED SAFETY SYSTEMSAddresseeAll holders of operating licenses for nuclear power reactors.purposeThe U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alertaddressees to several recent events in which inadequate or poorly controlled, non-safety-related maintenance activities resulted in unnecessary challenges to safety systems. It isexpected that recipients will review the information for applicability to their facilities and consideraction, as appropriate to avoid similar problems. However, suggestions contained in thisinformation notice are not NRC requirements; therefore, no specific action or written responseis required. | | {{#Wiki_filter:Acre |
| | |
| | ~0- f9 UNITED STATES |
| | |
| | NUCLEAR REGULATORY COMMISSION |
| | |
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| | |
| | WASHINGTON, D.C. 20555-0001 September 18, 1998 NRC INFORMATION NOTICE 98-36: INADEQUATE OR POORLY CONTROLLED, NON- |
| | SAFETY-RELATED MAINTENANCE ACTIVITIES |
| | |
| | UNNECESSARILY CHALLENGED SAFETY SYSTEMS |
| | |
| | Addressee |
| | |
| | All holders of operating licenses for nuclear power reactors. |
| | |
| | purpose |
| | |
| | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alert |
| | |
| | addressees to several recent events in which inadequate or poorly controlled, non-safety- related maintenance activities resulted in unnecessary challenges to safety systems. It is |
| | |
| | expected that recipients will review the information for applicability to their facilities and consider |
| | |
| | action, as appropriate to avoid similar problems. However, suggestions contained in this |
| | |
| | information notice are not NRC requirements; therefore, no specific action or written response |
| | |
| | is required. |
|
| |
|
| ==Description of Circumstances== | | ==Description of Circumstances== |
| BRAIDWOOD UNIT 2On January 18, 1996, with Braidwood Unit 2 operating at full power, .offsite power was lost.Inadequately secured roofing repair materials located on the roof of the adjacent servicebuilding were blown off the roof during a rain storm, causing a phase-to-ground arc on one oftwo station auxiliary transformers (SATs). As designed, the second SAT tripped when the firstSAT failed. Both emergency diesel generators (EDGs) automatically started and all safe-shutdown loads automatically sequenced on to the engineered safety feature (ESF) buses. Allautomatic bus transfers occurred as designed, maintaining power to non-ESF buses from theunit auxiliary transformers (UATs). The reactor remained stable at full power throughout theevent. To restore offsite power to Unit 2, the licensee cross-tied both Unit 2 ESF buses to therespective ESF buses of Unit 1, which also remained at full power throughout the event.Inspection of the faulted SAT revealed damage to (1) the Phase B and C bushings and (2) agas detector relay on top of the transformer where heavy arcing occurred. The licenseedetermined that the Initiating event was a Phase C arc-to-ground, followed by a Phase B tovNOrT g NO -98T- goz 98 0e 8<9809 td n
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| f IN 98-36September 18, 1998 Phase C arc. A 345-kilovolt switchyard breaker, Which connected the SAT to the switchyardring bus, was also damaged. Approximately one square foot of the Phase B bushing wasblown out.BYRON UNIT IOn May 23, 1996, with the Unit 1 reactor shut down In excess of a month for a refueling outage,offsite power was lost when one of the two Unit I SATs Isolated because of a Phase A toPhase B current differential relay operation. The second SAT tripped as designed when thefirst SAT failed. Both EDGs automatically started and all safe-shutdown loads automaticallysequenced on to the ESF buses. Because the reactor was shut down, power to non-ESFbuses was lost and two service water pumps and a station air compressor common to bothByron units tripped. Without the service water pumps, Unit 2, which was operating at fullpower, had no cooling water to many loads, including the main generator auxiliaries, station aircompressors, condensate pumps, and condensate booster pumps. Subsequently, Unit 2 wasmanually tripped.The licensee determined that the SAT that initially tripped underwent a phase-to-ground fault ona Phase B insulator. The failed insulator was located outdoors, about halfway between the SATand the auxiliary building. After Initiating, the arc continued down the bus bar, Increasing inwidth until It involved the other two phases. Air and water present in the bus bar duct washeated by the arc and resulted in pressurization of the duct.Chronic water leakage through inadequately caulked Insulator mounting holes and through animproperly compressed gasket caused degradation of the insulator metal inserts and Insulatormaterial between these inserts. Eventually, the bus flashed to ground through the degradedinsulator and initiated the transient.PERRYOn June 5, 1997, Perry was operating at full power when an automatic reactor scram occurredfollowing a three-phase fault in one of two high-voltage secondary winding terminationcompartments of the UAT. The fault resulted in the actuation of the auxiliary transformer phasedifferential relay, a main generator lockout, a main turbine trip, and fast closure of the turbinecontrol valves.At the time of the transient, safety-related electrical loads were being supplied by the in-servicestartup transformer. The non-safety-related electrical loads supplied by the transformerautomatically transferred to the startup transformer except for the bus that was faulted.Operators stabilized the plant without major complication.The licensee determined that the fault had developed as a result of an accumulation of moistureand dust that had entered the termination compartment housing where a 2-Inch-long piece ofgasket material was missing from the compartment housing-to-transformer sealing surface.The missing piece of gasket material may have been lost during work performed when | | ===BRAIDWOOD UNIT 2=== |
| | On January 18, 1996, with Braidwood Unit 2 operating at full power, .offsite power was lost. |
| | |
| | Inadequately secured roofing repair materials located on the roof of the adjacent service |
| | |
| | building were blown off the roof during a rain storm, causing a phase-to-ground arc on one of |
| | |
| | two station auxiliary transformers (SATs). As designed, the second SAT tripped when the first |
| | |
| | SAT failed. Both emergency diesel generators (EDGs) automatically started and all safe- shutdown loads automatically sequenced on to the engineered safety feature (ESF) buses. All |
| | |
| | automatic bus transfers occurred as designed, maintaining power to non-ESF buses from the |
| | |
| | unit auxiliary transformers (UATs). The reactor remained stable at full power throughout the |
| | |
| | event. To restore offsite power to Unit 2, the licensee cross-tied both Unit 2 ESF buses to the |
| | |
| | respective ESF buses of Unit 1, which also remained at full power throughout the event. |
| | |
| | Inspection of the faulted SAT revealed damage to (1) the Phase B and C bushings and (2) a |
| | |
| | gas detector relay on top of the transformer where heavy arcing occurred. The licensee |
| | |
| | determined that the Initiating event was a Phase C arc-to-ground, followed by a Phase B to |
| | |
| | vNOrT g NO -98T- goz 98 0e 8 |
| | <9809 td n |
| | |
| | f IN 98-36 September 18, 1998 Phase C arc. A 345-kilovolt switchyard breaker, Which connected the SAT to the switchyard |
| | |
| | ring bus, was also damaged. Approximately one square foot of the Phase B bushing was |
| | |
| | blown out. |
| | |
| | ===BYRON UNIT I=== |
| | On May 23, 1996, with the Unit 1 reactor shut down In excess of a month for a refueling outage, offsite power was lost when one of the two Unit I SATs Isolated because of a Phase A to |
| | |
| | Phase B current differential relay operation. The second SAT tripped as designed when the |
| | |
| | first SAT failed. Both EDGs automatically started and all safe-shutdown loads automatically |
| | |
| | sequenced on to the ESF buses. Because the reactor was shut down, power to non-ESF |
| | |
| | buses was lost and two service water pumps and a station air compressor common to both |
| | |
| | Byron units tripped. Without the service water pumps, Unit 2, which was operating at full |
| | |
| | power, had no cooling water to many loads, including the main generator auxiliaries, station air |
| | |
| | compressors, condensate pumps, and condensate booster pumps. Subsequently, Unit 2 was |
|
| |
|
| K>1IN 98-36September 18, 1998 replacing the auxiliary transformer following failure of the transformer on May 30, 1996. Thecause of that failure was attributed to Inadequate original design or poor assembly practices orboth.POINT BEACH UNIT IDuring a severe storm on January 8, 1998, a ground In the low-voltage-side bus duct causedthe failure of the Unit I SAT. This failure and a failure of the 13.8-kilovolt automatic bus transferto the Unit 2 SAT resulted in the loss of normal power to the Unit I safeguards buses. TheEDGs subsequently started and restored power to the buses. Unit I remained at 98 percentpower throughout the transient. Unit 2 was in cold shutdown.The licensee attributed the failure of the transformer to the buildup of condensation internal tothe buses and long-term insulation degradation In the bus duct on the low-voltage side of thetransformer. Before the transformer failed, the circuit breaker for a heater designed to keep thebus duct dry would not remain closed. Consequently, in August 1996, the licensee left thecircuit breaker open and wrote a work order for its repair. However, work schedulers did notrecognize that the bus duct heater was inoperable with the circuit breaker open, and the workorder was erroneously classified as "minor maintenance" and given low priority. At the time thetransformer failed, the work order was in the "backlog' of maintenance Items. In addition to theinoperable heater, the:licensee determined that the lack of a routine inspection program for thebus ducts may have contributed to the event. Inspection of the bus ducts after the transformerfailed revealed insulation breakdown that would likely have been Identified through a periodicInspection program.DiscussionThese events illustrate the potentially significant consequences of inadequate or poorlyperformed maintenance activities on non-safety-related plant components. Unnecessarychallenges to plant safety systems or control room operators or both could result frominadequate control or inattention to detail during non-safety-related maintenance activities. Thepotential impact on safety systems of such activities as the re-roofing of nuclear power plantsupport buildings, the Installation of gaskets, or the caulking of outdoor components, couldeasily be overlooked. In addition, several of the events discussed here highlight the need forlicensees to have better control over the maintenance activities of contractor and non-stationutility employees, and the need for thorough periodic walkdowns or preventive maintenance onauxiliary transformers and the associated outdoor bus ducts.
| | manually tripped. |
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| IN 98-36September 18, 1998 This information notice requires no specific action or written response. However, recipients arereminded that they are required to consider Industry-wide operating experience (including NRCINs) where practical, when setting goals and performing periodic evaluations under Section50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear PowerPlants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have any questionsabout the information In this notice, please contact one of the technical contacts listed below orthe appropriate Office of Nuclear Reactor Regulation (NRR) project manager.eJack , Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Mike Kunowski, Region IlIl John Neisler, Region IlIl630-829-9816 630429-9718E-mail: mak3@nrc.gov E-mail: jhn@nrc.govAttachment: List of Recently Issued NRC Information Notices
| | The licensee determined that the SAT that initially tripped underwent a phase-to-ground fault on |
|
| |
|
| A,(ttachment 1IN 98-36September 18, 1998 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformationNotice No.Date ofIssuanceSubject98-35Threat Assessments andConsideration of HeightenedPhysical Protection Measures914/98Issued toAll U.S. NRC fuel cycle facilitiespower and non-power reactorlicensees (Safeguard issues, notfor public disclosure.)98-3498-3398-3298-31NRC Configuration ControlErrorsNRC Regulations ProhibitAgreements that restrict orDiscourage an Employee fromParticipating In Protected ActivitiesProblems Associated with Post-Fire Safe-Shutdown CircuitAnalyses8/28/9881281988126198All holders of Operating licensesfor nuclear power reactors, exceptfor those who have ceasedoperations and have certified thatfuel has been permanentlyremoved from the reactor vesselAll holders of a U.S. NuclearRegulatory Commission (NRC)license.All holders of operating licensesfor nuclear power reactors, exceptthose who have permanentlyceased operations and havecertified that fuel has beenpermanently removed form thereactorAll holders of operating licencesfor nuclear power reactors, exceptthose licensees that havepermanently ceased operationsand have certified that fuel hasbeen permanently removed fromthe reactor vessel.Fire Protection System Design 8/26/98Deficiencies and Common-ModeFlooding of Emergency Core CoolingSystem Rooms at Washington NuclearProject Unit 2OL = Operating LicenseCP = Construction Permit
| | a Phase B insulator. The failed insulator was located outdoors, about halfway between the SAT |
|
| |
|
| -IN 98-36September 18, 1998 IN 98-xxSeptember xx, 1998 I
| | and the auxiliary building. After Initiating, the arc continued down the bus bar, Increasing in |
|
| |
|
| }} | | width until It involved the other two phases. Air and water present in the bus bar duct was |
| | |
| | heated by the arc and resulted in pressurization of the duct. |
| | |
| | Chronic water leakage through inadequately caulked Insulator mounting holes and through an |
| | |
| | improperly compressed gasket caused degradation of the insulator metal inserts and Insulator |
| | |
| | material between these inserts. Eventually, the bus flashed to ground through the degraded |
| | |
| | insulator and initiated the transient. |
| | |
| | PERRY |
| | |
| | On June 5, 1997, Perry was operating at full power when an automatic reactor scram occurred |
| | |
| | following a three-phase fault in one of two high-voltage secondary winding termination |
| | |
| | compartments of the UAT. The fault resulted in the actuation of the auxiliary transformer phase |
| | |
| | differential relay, a main generator lockout, a main turbine trip, and fast closure of the turbine |
| | |
| | control valves. |
| | |
| | At the time of the transient, safety-related electrical loads were being supplied by the in-service |
| | |
| | startup transformer. The non-safety-related electrical loads supplied by the transformer |
| | |
| | automatically transferred to the startup transformer except for the bus that was faulted. |
| | |
| | Operators stabilized the plant without major complication. |
| | |
| | The licensee determined that the fault had developed as a result of an accumulation of moisture |
| | |
| | and dust that had entered the termination compartment housing where a 2-Inch-long piece of |
| | |
| | gasket material was missing from the compartment housing-to-transformer sealing surface. |
| | |
| | The missing piece of gasket material may have been lost during work performed when |
| | |
| | K>1 IN 98-36 September 18, 1998 replacing the auxiliary transformer following failure of the transformer on May 30, 1996. The |
| | |
| | cause of that failure was attributed to Inadequate original design or poor assembly practices or |
| | |
| | both. |
| | |
| | ===POINT BEACH UNIT I=== |
| | During a severe storm on January 8, 1998, a ground In the low-voltage-side bus duct caused |
| | |
| | the failure of the Unit I SAT. This failure and a failure of the 13.8-kilovolt automatic bus transfer |
| | |
| | to the Unit 2 SAT resulted in the loss of normal power to the Unit I safeguards buses. The |
| | |
| | EDGs subsequently started and restored power to the buses. Unit I remained at 98 percent |
| | |
| | power throughout the transient. Unit 2 was in cold shutdown. |
| | |
| | The licensee attributed the failure of the transformer to the buildup of condensation internal to |
| | |
| | the buses and long-term insulation degradation In the bus duct on the low-voltage side of the |
| | |
| | transformer. Before the transformer failed, the circuit breaker for a heater designed to keep the |
| | |
| | bus duct dry would not remain closed. Consequently, in August 1996, the licensee left the |
| | |
| | circuit breaker open and wrote a work order for its repair. However, work schedulers did not |
| | |
| | recognize that the bus duct heater was inoperable with the circuit breaker open, and the work |
| | |
| | order was erroneously classified as "minor maintenance" and given low priority. At the time the |
| | |
| | transformer failed, the work order was in the "backlog' of maintenance Items. In addition to the |
| | |
| | inoperable heater, the:licensee determined that the lack of a routine inspection program for the |
| | |
| | bus ducts may have contributed to the event. Inspection of the bus ducts after the transformer |
| | |
| | failed revealed insulation breakdown that would likely have been Identified through a periodic |
| | |
| | Inspection program. |
| | |
| | Discussion |
| | |
| | These events illustrate the potentially significant consequences of inadequate or poorly |
| | |
| | performed maintenance activities on non-safety-related plant components. Unnecessary |
| | |
| | challenges to plant safety systems or control room operators or both could result from |
| | |
| | inadequate control or inattention to detail during non-safety-related maintenance activities. The |
| | |
| | potential impact on safety systems of such activities as the re-roofing of nuclear power plant |
| | |
| | support buildings, the Installation of gaskets, or the caulking of outdoor components, could |
| | |
| | easily be overlooked. In addition, several of the events discussed here highlight the need for |
| | |
| | licensees to have better control over the maintenance activities of contractor and non-station |
| | |
| | utility employees, and the need for thorough periodic walkdowns or preventive maintenance on |
| | |
| | auxiliary transformers and the associated outdoor bus ducts. |
| | |
| | IN 98-36 September 18, 1998 This information notice requires no specific action or written response. However, recipients are |
| | |
| | reminded that they are required to consider Industry-wide operating experience (including NRC |
| | |
| | INs) where practical, when setting goals and performing periodic evaluations under Section |
| | |
| | 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power |
| | |
| | Plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions |
| | |
| | about the information Inthis notice, please contact one of the technical contacts listed below or |
| | |
| | the appropriate Office of Nuclear Reactor Regulation (NRR) project manager. |
| | |
| | , Acting Director |
| | |
| | eJack |
| | |
| | Division of Reactor Program Management |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical contacts: Mike Kunowski, Region IlIl John Neisler, Region IlIl |
| | |
| | 630-829-9816 630429-9718 E-mail: mak3@nrc.gov E-mail: jhn@nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | A,(ttachment 1 IN 98-36 September 18, 1998 LIST OF RECENTLY ISSUED |
| | |
| | NRC INFORMATION NOTICES |
| | |
| | Information Date of |
| | |
| | Notice No. Subject Issuance Issued to |
| | |
| | 98-35 Threat Assessments and 914/98 All U.S. NRC fuel cycle facilities |
| | |
| | Consideration of Heightened power and non-power reactor |
| | |
| | Physical Protection Measures licensees (Safeguard issues, not |
| | |
| | for public disclosure.) |
| | 98-34 NRC Configuration Control 8/28/98 All holders of Operating licenses |
| | |
| | Errors for nuclear power reactors, except |
| | |
| | for those who have ceased |
| | |
| | operations and have certified that |
| | |
| | fuel has been permanently |
| | |
| | removed from the reactor vessel |
| | |
| | 98-33 NRC Regulations Prohibit 8128198 All holders of a U.S. Nuclear |
| | |
| | Agreements that restrict or Regulatory Commission (NRC) |
| | Discourage an Employee from license. |
| | |
| | Participating In Protected Activities |
| | |
| | 98-32 Problems Associated with Post- 8126198 All holders of operating licenses |
| | |
| | Fire Safe-Shutdown Circuit for nuclear power reactors, except |
| | |
| | Analyses those who have permanently |
| | |
| | ceased operations and have |
| | |
| | certified that fuel has been |
| | |
| | permanently removed form the |
| | |
| | reactor |
| | |
| | 98-31 Fire Protection System Design 8/26/98 All holders of operating licences |
| | |
| | Deficiencies and Common-Mode for nuclear power reactors, except |
| | |
| | Flooding of Emergency Core Cooling those licensees that have |
| | |
| | System Rooms at Washington Nuclear permanently ceased operations |
| | |
| | Project Unit 2 and have certified that fuel has |
| | |
| | been permanently removed from |
| | |
| | the reactor vessel. |
| | |
| | OL = Operating License |
| | |
| | CP = Construction Permit |
| | |
| | - IN 98-36 September 18, 1998 This information notice requires no specific action or written response. However, recipients are |
| | |
| | reminded that they are required to consider industry-wide operating experience (including NRC |
| | |
| | INs) where practical, when setting goals and performing periodic evaluations under Section |
| | |
| | 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power |
| | |
| | Plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions |
| | |
| | about the information in this notice, please contact one of the technical contacts listed below or |
| | |
| | the appropriate Office of Nuclear Reactor Regulation (NRR) project manager. |
| | |
| | Jack W. Roe, Acting Director |
| | |
| | Division of Reactor Program Management |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical contacts: Mike Kunowski, Region IlIl John Neisler, Region IlIl |
| | |
| | 630-829-9816 630-829-9718 E-mail: mak3@nrc.gov E-mail: jhn@nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Information Notices |
| | |
| | *See previous concurrence & e. |
| | |
| | C,,tt |
| | |
| | **E-mail concurrence c<f() |
| | DOCUMENT NAME: G:\NICK\REGION.IN |
| | |
| | To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure E=Copy with attachmentlenclosure N = No copy |
| | |
| | OFFICE PECB I Tech EdI Reg III [ Regil I PECB I C:PECB l_ji D M |
| | |
| | NAME NFields* RSanders* MKunowski** JNeisler** RDennig* JStolz* JRo |
| | |
| | DATE 09/03/98 08/26/98 09/03/98 Ii09/03/98 09/14/98 J09/14/98 \/98 OFFICIAL RECORD COPY |
| | |
| | IN 98-xx |
| | |
| | September xx, 1998 This information notice requires no specific action or written response. However, recipie are |
| | |
| | reminded that they are required to consider industry-wide operating experience (includ g NRC |
| | |
| | INs) where practical, when setting goals and performing periodic evaluations under ection |
| | |
| | 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclea ower |
| | |
| | Plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have ny questions |
| | |
| | about the information in this notice, please contact one of the technical con cts listed below or |
| | |
| | the appropriate Office of Nuclear Reactor Regulation (NRR) project man er. |
| | |
| | Jack W. Roe, Acting irector |
| | |
| | Division of Reactor rogram Management |
| | |
| | Office of Nuclea eactor Regulation |
| | |
| | Technical contacts: Mike Kunowski, Region IlIl Joh eisler, Region IlIl |
| | |
| | 630-829-9816 63 -829-9718 E-mail: mak3@nrc.gov -mail: jhn@nrc.gov |
| | |
| | Attachment: List of Recently Issued NRC Info tion Notices |
| | |
| | DOCUMENT NAME: G:\NICK\REGION.IN |
| | |
| | To receive a copy of this document, Indicate in the box C=Copy wlo attachmentenclosure E=Copy with attachmentlenclosure N = No copy |
| | |
| | OFFICE PECB. I _ Tech Ed I _ Reg I lI _I Reg 11 l 1/E "ECB (A)D:DRPM l |
| | |
| | NAME NFiells' { RSanders MKu owsk Jeisler ennig l l JRoe |
| | |
| | l DATE /3/98 1SW98 17/3/98 15/3198 lH/ 48 q/l98 l I /98 OFFICIAL RECORD COPY I}} |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety SystemsML031040558 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
09/18/1998 |
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From: |
Roe J Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-98-036, NUDOCS 9809210079 |
Download: ML031040558 (7) |
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Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
Acre
~0- f9 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 September 18, 1998 NRC INFORMATION NOTICE 98-36: INADEQUATE OR POORLY CONTROLLED, NON-
SAFETY-RELATED MAINTENANCE ACTIVITIES
UNNECESSARILY CHALLENGED SAFETY SYSTEMS
Addressee
All holders of operating licenses for nuclear power reactors.
purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to alert
addressees to several recent events in which inadequate or poorly controlled, non-safety- related maintenance activities resulted in unnecessary challenges to safety systems. It is
expected that recipients will review the information for applicability to their facilities and consider
action, as appropriate to avoid similar problems. However, suggestions contained in this
information notice are not NRC requirements; therefore, no specific action or written response
is required.
Description of Circumstances
BRAIDWOOD UNIT 2
On January 18, 1996, with Braidwood Unit 2 operating at full power, .offsite power was lost.
Inadequately secured roofing repair materials located on the roof of the adjacent service
building were blown off the roof during a rain storm, causing a phase-to-ground arc on one of
two station auxiliary transformers (SATs). As designed, the second SAT tripped when the first
SAT failed. Both emergency diesel generators (EDGs) automatically started and all safe- shutdown loads automatically sequenced on to the engineered safety feature (ESF) buses. All
automatic bus transfers occurred as designed, maintaining power to non-ESF buses from the
unit auxiliary transformers (UATs). The reactor remained stable at full power throughout the
event. To restore offsite power to Unit 2, the licensee cross-tied both Unit 2 ESF buses to the
respective ESF buses of Unit 1, which also remained at full power throughout the event.
Inspection of the faulted SAT revealed damage to (1) the Phase B and C bushings and (2) a
gas detector relay on top of the transformer where heavy arcing occurred. The licensee
determined that the Initiating event was a Phase C arc-to-ground, followed by a Phase B to
vNOrT g NO -98T- goz 98 0e 8
<9809 td n
f IN 98-36 September 18, 1998 Phase C arc. A 345-kilovolt switchyard breaker, Which connected the SAT to the switchyard
ring bus, was also damaged. Approximately one square foot of the Phase B bushing was
blown out.
BYRON UNIT I
On May 23, 1996, with the Unit 1 reactor shut down In excess of a month for a refueling outage, offsite power was lost when one of the two Unit I SATs Isolated because of a Phase A to
Phase B current differential relay operation. The second SAT tripped as designed when the
first SAT failed. Both EDGs automatically started and all safe-shutdown loads automatically
sequenced on to the ESF buses. Because the reactor was shut down, power to non-ESF
buses was lost and two service water pumps and a station air compressor common to both
Byron units tripped. Without the service water pumps, Unit 2, which was operating at full
power, had no cooling water to many loads, including the main generator auxiliaries, station air
compressors, condensate pumps, and condensate booster pumps. Subsequently, Unit 2 was
manually tripped.
The licensee determined that the SAT that initially tripped underwent a phase-to-ground fault on
a Phase B insulator. The failed insulator was located outdoors, about halfway between the SAT
and the auxiliary building. After Initiating, the arc continued down the bus bar, Increasing in
width until It involved the other two phases. Air and water present in the bus bar duct was
heated by the arc and resulted in pressurization of the duct.
Chronic water leakage through inadequately caulked Insulator mounting holes and through an
improperly compressed gasket caused degradation of the insulator metal inserts and Insulator
material between these inserts. Eventually, the bus flashed to ground through the degraded
insulator and initiated the transient.
PERRY
On June 5, 1997, Perry was operating at full power when an automatic reactor scram occurred
following a three-phase fault in one of two high-voltage secondary winding termination
compartments of the UAT. The fault resulted in the actuation of the auxiliary transformer phase
differential relay, a main generator lockout, a main turbine trip, and fast closure of the turbine
control valves.
At the time of the transient, safety-related electrical loads were being supplied by the in-service
startup transformer. The non-safety-related electrical loads supplied by the transformer
automatically transferred to the startup transformer except for the bus that was faulted.
Operators stabilized the plant without major complication.
The licensee determined that the fault had developed as a result of an accumulation of moisture
and dust that had entered the termination compartment housing where a 2-Inch-long piece of
gasket material was missing from the compartment housing-to-transformer sealing surface.
The missing piece of gasket material may have been lost during work performed when
K>1 IN 98-36 September 18, 1998 replacing the auxiliary transformer following failure of the transformer on May 30, 1996. The
cause of that failure was attributed to Inadequate original design or poor assembly practices or
both.
POINT BEACH UNIT I
During a severe storm on January 8, 1998, a ground In the low-voltage-side bus duct caused
the failure of the Unit I SAT. This failure and a failure of the 13.8-kilovolt automatic bus transfer
to the Unit 2 SAT resulted in the loss of normal power to the Unit I safeguards buses. The
EDGs subsequently started and restored power to the buses. Unit I remained at 98 percent
power throughout the transient. Unit 2 was in cold shutdown.
The licensee attributed the failure of the transformer to the buildup of condensation internal to
the buses and long-term insulation degradation In the bus duct on the low-voltage side of the
transformer. Before the transformer failed, the circuit breaker for a heater designed to keep the
bus duct dry would not remain closed. Consequently, in August 1996, the licensee left the
circuit breaker open and wrote a work order for its repair. However, work schedulers did not
recognize that the bus duct heater was inoperable with the circuit breaker open, and the work
order was erroneously classified as "minor maintenance" and given low priority. At the time the
transformer failed, the work order was in the "backlog' of maintenance Items. In addition to the
inoperable heater, the:licensee determined that the lack of a routine inspection program for the
bus ducts may have contributed to the event. Inspection of the bus ducts after the transformer
failed revealed insulation breakdown that would likely have been Identified through a periodic
Inspection program.
Discussion
These events illustrate the potentially significant consequences of inadequate or poorly
performed maintenance activities on non-safety-related plant components. Unnecessary
challenges to plant safety systems or control room operators or both could result from
inadequate control or inattention to detail during non-safety-related maintenance activities. The
potential impact on safety systems of such activities as the re-roofing of nuclear power plant
support buildings, the Installation of gaskets, or the caulking of outdoor components, could
easily be overlooked. In addition, several of the events discussed here highlight the need for
licensees to have better control over the maintenance activities of contractor and non-station
utility employees, and the need for thorough periodic walkdowns or preventive maintenance on
auxiliary transformers and the associated outdoor bus ducts.
IN 98-36 September 18, 1998 This information notice requires no specific action or written response. However, recipients are
reminded that they are required to consider Industry-wide operating experience (including NRC
INs) where practical, when setting goals and performing periodic evaluations under Section
50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power
Plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions
about the information Inthis notice, please contact one of the technical contacts listed below or
the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
, Acting Director
eJack
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Mike Kunowski, Region IlIl John Neisler, Region IlIl
630-829-9816 630429-9718 E-mail: mak3@nrc.gov E-mail: jhn@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
A,(ttachment 1 IN 98-36 September 18, 1998 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
98-35 Threat Assessments and 914/98 All U.S. NRC fuel cycle facilities
Consideration of Heightened power and non-power reactor
Physical Protection Measures licensees (Safeguard issues, not
for public disclosure.)
98-34 NRC Configuration Control 8/28/98 All holders of Operating licenses
Errors for nuclear power reactors, except
for those who have ceased
operations and have certified that
fuel has been permanently
removed from the reactor vessel
98-33 NRC Regulations Prohibit 8128198 All holders of a U.S. Nuclear
Agreements that restrict or Regulatory Commission (NRC)
Discourage an Employee from license.
Participating In Protected Activities
98-32 Problems Associated with Post- 8126198 All holders of operating licenses
Fire Safe-Shutdown Circuit for nuclear power reactors, except
Analyses those who have permanently
ceased operations and have
certified that fuel has been
permanently removed form the
reactor
98-31 Fire Protection System Design 8/26/98 All holders of operating licences
Deficiencies and Common-Mode for nuclear power reactors, except
Flooding of Emergency Core Cooling those licensees that have
System Rooms at Washington Nuclear permanently ceased operations
Project Unit 2 and have certified that fuel has
been permanently removed from
the reactor vessel.
OL = Operating License
CP = Construction Permit
- IN 98-36 September 18, 1998 This information notice requires no specific action or written response. However, recipients are
reminded that they are required to consider industry-wide operating experience (including NRC
INs) where practical, when setting goals and performing periodic evaluations under Section
50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power
Plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have any questions
about the information in this notice, please contact one of the technical contacts listed below or
the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Mike Kunowski, Region IlIl John Neisler, Region IlIl
630-829-9816 630-829-9718 E-mail: mak3@nrc.gov E-mail: jhn@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
- See previous concurrence & e.
C,,tt
DOCUMENT NAME: G:\NICK\REGION.IN
To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure E=Copy with attachmentlenclosure N = No copy
OFFICE PECB I Tech EdI Reg III [ Regil I PECB I C:PECB l_ji D M
NAME NFields* RSanders* MKunowski** JNeisler** RDennig* JStolz* JRo
DATE 09/03/98 08/26/98 09/03/98 Ii09/03/98 09/14/98 J09/14/98 \/98 OFFICIAL RECORD COPY
IN 98-xx
September xx, 1998 This information notice requires no specific action or written response. However, recipie are
reminded that they are required to consider industry-wide operating experience (includ g NRC
INs) where practical, when setting goals and performing periodic evaluations under ection
50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclea ower
Plants," of Part 50 of Title 10 of the Code of Federal Regulations. If you have ny questions
about the information in this notice, please contact one of the technical con cts listed below or
the appropriate Office of Nuclear Reactor Regulation (NRR) project man er.
Jack W. Roe, Acting irector
Division of Reactor rogram Management
Office of Nuclea eactor Regulation
Technical contacts: Mike Kunowski, Region IlIl Joh eisler, Region IlIl
630-829-9816 63 -829-9718 E-mail: mak3@nrc.gov -mail: jhn@nrc.gov
Attachment: List of Recently Issued NRC Info tion Notices
DOCUMENT NAME: G:\NICK\REGION.IN
To receive a copy of this document, Indicate in the box C=Copy wlo attachmentenclosure E=Copy with attachmentlenclosure N = No copy
OFFICE PECB. I _ Tech Ed I _ Reg I lI _I Reg 11 l 1/E "ECB (A)D:DRPM l
NAME NFiells' { RSanders MKu owsk Jeisler ennig l l JRoe
l DATE /3/98 1SW98 17/3/98 15/3198 lH/ 48 q/l98 l I /98 OFFICIAL RECORD COPY I
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list | - Information Notice 1998-01, Thefts of Portable Gauges (15 January 1998, Topic: Shutdown Margin, Moisture-Density Gauge, Stolen)
- Information Notice 1998-02, Nuclear Power Plant Cold Weather Problems and Protective Measures (21 January 1998)
- Information Notice 1998-03, Inadequate Verification of Overcurrent Trip Setpoints in Metal-Clad, Low-Voltage Circuit Breakers (21 January 1998)
- Information Notice 1998-04, 1997 Enforcement Sanctions for Deliberate Violations of NRC Employee Protection Requirements (9 February 1998)
- Information Notice 1998-05, Criminal History Record Information (11 February 1998)
- Information Notice 1998-06, Unauthorized Use of License to Obtain Radioactive Materials, and Its Implication Under the Expanded Title 18 of the U.S. Code (19 February 1998)
- Information Notice 1998-07, Offsite Power Reliability Challenges from Industry Deregulation (27 February 1998)
- Information Notice 1998-08, Information Likely to Be Requested If an Emergency is Declared (2 March 1998)
- Information Notice 1998-08, Information Likely to Be Requested If an Emergency Is Declared (2 March 1998)
- Information Notice 1998-09, Collapse of an Isocam II, Dual-Headed Nuclear Medicine Gamma Camera (5 March 1998)
- Information Notice 1998-10, Probable Misadministrations Occurring During Intravascular Brachytherapy with Novoste Beta-cath System (9 March 1998, Topic: Brachytherapy)
- Information Notice 1998-11, Cracking of Reactor Vessel Internal Baffle Former Bolts in Foreign Plants (25 March 1998, Topic: Fire Barrier, Brachytherapy)
- Information Notice 1998-12, Licensees' Responsibilities Regarding Reporting & Follow-up Requirements for Nuclear-Powered Pacemakers (3 April 1998, Topic: Fire Barrier, Brachytherapy, Stolen)
- Information Notice 1998-13, Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality (20 April 1998, Topic: Fire Barrier, VT-2, Pressure Boundary Leakage, Brachytherapy)
- Information Notice 1998-14, Undocumented Changes to Non-Power Reactor Safety System Wiring (20 April 1998, Topic: Brachytherapy, Failure to Scram)
- Information Notice 1998-15, Integrity of Operator Licensing Examinations (20 April 1998, Topic: Fire Barrier, Job Performance Measure)
- Information Notice 1998-16, Inadequate Operational Checks of Alarm Ratemeters (30 April 1998, Topic: Brachytherapy)
- Information Notice 1998-17, Federal Bureau of Investigation'S (FBI) Awareness of National Security Issues and Response (ANSIR) Program (7 May 1998)
- Information Notice 1998-17, Federal Bureau of Investigation'S (FBI) Awareness of National Security Issues and Response (Ansir) Program (7 May 1998, Topic: Brachytherapy)
- Information Notice 1998-18, Recent Contamination Incidences Resulting from Failure to Perform Adequate Surveys (13 May 1998, Topic: Brachytherapy)
- Information Notice 1998-19, Shaft Binding in General Electric Type Sbm Control Switches (3 June 1998)
- Information Notice 1998-20, Problems with Emergency Preparedness Respiratory Protection Programs (3 June 1998, Topic: Brachytherapy)
- Information Notice 1998-21, Potential Deficiency of Electrical Cable/Connection Systems (4 June 1998)
- Information Notice 1998-22, Deficiencies Identified During NRC Design Inspections (17 June 1998, Topic: Stroke time, Tornado Missile)
- Information Notice 1998-23, Crosby Relief Valve Setpoint Drift Problems Caused by Corrosion of Guide Ring (23 June 1998, Topic: Loop seal, Condition Adverse to Quality)
- Information Notice 1998-25, Loss of Inventory from Safety-Related Closed-Loop Cooling Water Systems (8 July 1998, Topic: Ultimate heat sink)
- Information Notice 1998-26, Settlement Monitoring and Inspection of Plant Structures Affected by Degradation of Porous Concrete Subfoundations (24 July 1998, Topic: Condition Adverse to Quality)
- Information Notice 1998-27, Steam Generator Tube End Cracking (24 July 1998)
- Information Notice 1998-28, Development of Systematic Sample Plan for Operator Licensing Examinations (31 July 1998)
- Information Notice 1998-29, Predicted Increase in Fuel Rod Cladding Oxidation (3 August 1998, Topic: Fuel cladding)
- Information Notice 1998-30, Effect of Year 2000 Computer Problem on NRC Licensees and Certificate Holders (12 August 1998, Topic: Brachytherapy)
- Information Notice 1998-31, Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2 (18 August 1998, Topic: Water hammer)
- Information Notice 1998-33, NRC Regulations Prohibit Agreements That Restrict or Discourage an Employee from Participating in Protected Activities (28 August 1998, Topic: Brachytherapy)
- Information Notice 1998-34, Configuration Control Errors (28 August 1998)
- Information Notice 1998-36, Inadequate or Poorly Controlled, Non-Safety-Related Maintenance Activities Unnecessarily Challenged Safety Systems (18 September 1998)
- Information Notice 1998-37, Eligibility of Operator License Applicants (1 October 1998)
- Information Notice 1998-38, Metal-Clad Circuit Breaker Maintenance Issues Identified by NRC Inspections (15 October 1998, Topic: Overtravel, Reactive Inspection)
- Information Notice 1998-39, Summary of Fitness-for-Duty Program Performance Reports for Calendar Years 1996 and 1997 (30 October 1998, Topic: Fitness for Duty)
- Information Notice 1998-40, Design Deficiencies Can Lead to Reduced ECCS Pump Net Positive Suction Head During Design-Basis Accidents (26 October 1998)
- Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators From Design Oversight (20 November 1998)
- Information Notice 1998-41, Spurious Shutdown of Emergency Diesel Generators from Design Oversight (20 November 1998)
- Information Notice 1998-42, Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements (1 December 1998)
- Information Notice 1998-43, Leaks in Emergency Diesel Generator Lubricating Oil & Jacket Cooling Water Piping (4 December 1998)
- Information Notice 1998-44, Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping (10 December 1998, Topic: Probabilistic Risk Assessment)
- Information Notice 1998-45, Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds (15 December 1998)
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